ASTM-C753 2009
$35.75
C753-04(2009) Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
Published By | Publication Date | Number of Pages |
ASTM | 2009 | 4 |
ASTM C753-04-Reapproved2009
Historical Standard: Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
ASTM C753
Scope
1.1 This specification covers nuclear-grade, sinterable uranium dioxide (UO2) powder. It applies to uranium dioxide powder containing uranium of any 235U concentration in the production of nuclear fuel pellets for use in nuclear reactors.
1.2 This specification recognizes the presence of reprocessed uranium in the fuel cycle and consequently defines isotopic limits for commercial grade UO2. Such commercial grade UO2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unreprocessed uranium. UO2 falling outside these limits cannot necessarily be regarded as equivalent and may thus need special provisions at the fuel fabrication plant or in the fuel design.
1.3 This specification does not include provisions for preventing criticality accidents or requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all international, national, or federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material.
1.4 This specification refers expressly to calcined UO2 powder before the addition of any die lubricant, binder, or pore former. If powder is sold with such additions or prepared as press feed, sampling procedures, allowable impurity contents, or powder physical requirements may need to be modified by agreement between the buyer and the seller.
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory requirements prior to use.
Keywords
nuclear fuel; powder; urania; uranium dioxide; Performance–nuclear materials/applications; Sinterability test; Urania; Uranium–specifications; Uranium dioxide powder (sinterable); Nuclear fuels (reactor)–specifications; Nuclear materials/applications–specifications
ICS Code
ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)
DOI: 10.1520/C0753-04R09
PDF Catalog
PDF Pages | PDF Title |
---|---|
1 | Scope Referenced Documents |
2 | Terminology Chemical Requirements Physical Requirements Sampling TABLE 1 |
3 | Test Methods Certification Packaging and Package Marking Quality Assurance Keywords X1. SINTERABILITY TEST X1.1 Purpose X1.2 Fabrication of Test Pellets |
4 | X1.3 Density Determination X1.4 Sintered Pellet Performance Test |